New concept of fast reactor (FR), i.e. the STFR (Spray Type FR), is proposed here to perform high burn-up of UO2 fuel or MOX fuel by the use of BWR technology, and to improve the backend process of discharged fuel. STFR can be realized by some important changes of BWR system, at 7.50MPa. In case of STFR, heat produced in the core is removed by the evaporation of sprayed hot water jetted to fuel with cross flow at 7.50MPa, and two phases (liquid and vapor) of coolant at high void ratio goes down to the bottom of PV (pressure vessel). This is an improved concept of BWR, which can be regarded as a breakthrough of FBR. This concept has not been listed in GEN IV. Future performance of STFR are as follows, (1) STFR can increase the fraction of direct fission of 238U with neutron reaction of higher energy than 1MeV, (2) STFR can burn the nuclear fuel to the higher burn-up (80 to 200GWd/Mg-HM) compared with BWR fuel burn-up. (3) Higher burn-up of fuel will reduce the frequency of reprocessing, so STFR can reduce the reprocessing cost per power production. (4) STFR can reduce the remains of Pu and MA (Minor Actinides: Np, Am, Cm etc.) in discharged fuel.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4687-3
PROCEEDINGS PAPER
Hard Spectrum STFR (Spray Type Fast Reactor) Cooled by Water at 7.5 MPa Available to Purchase
Asashi Kitamoto,
Asashi Kitamoto
Institute of Research and Innovation, Kashiwa, Chiba, Japan
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Yasunori Ohoka
Yasunori Ohoka
Tokyo Institute of Technology, Tokyo, Japan
Search for other works by this author on:
Asashi Kitamoto
Institute of Research and Innovation, Kashiwa, Chiba, Japan
Yasunori Ohoka
Tokyo Institute of Technology, Tokyo, Japan
Paper No:
ICONE12-49382, pp. 475-484; 10 pages
Published Online:
November 17, 2008
Citation
Kitamoto, A, & Ohoka, Y. "Hard Spectrum STFR (Spray Type Fast Reactor) Cooled by Water at 7.5 MPa." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 1. Arlington, Virginia, USA. April 25–29, 2004. pp. 475-484. ASME. https://doi.org/10.1115/ICONE12-49382
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